Text

Amend 125 to License DPR-72,replacing cycle-specific Parameter Limits W/Ref to Core Operating Limits Rept in Plant Tech Specs
	ML20011E465
Person / Time
Site:	Crystal River
Issue date:	01/31/1990
From:	Berkow H; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20011E466	List: ML20011E465; ML20011E467;
References
	NUDOCS 9002140127
	Download: ML20011E465 (38)
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UNITED STATES

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g NUCLEAR REGULATORY COMMISSION j

WASHINGTON, D C. 20665

\\,.....f FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEE 5 BURG CITY OF NEW SMYRNA, BEACH AND UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEBRING UTILITIES CCMMISSION SEMUl0LE ELECTRIC COOPERATIVE, INC.

CITY OF TALLAHASSEE.

DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 125 License No. DPR-72 1..

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The application for amendment by Florida Power Corporation, et al.

(the licensees) dated March 22, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is-reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The-issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; ano E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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Accordingly, the license is anwnded by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. DPR-72 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.125, are hereby incorporated in the license.

Florida Power Corporation shall operate the facility in-

.accordance with the Technical Specifications.

3.

This license anendnent is effective inanediately and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION M

W He bert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/11 Office of Nuclear Peactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

January 31, 1990

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ATTACHMENT TO LICENSE AMENDMENT NO.125 FACILITY OPERATING LICENSE NO. DPR-72 00CKET NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness, Remove Insert o

la la 1-8 1-8 3/4 1-19 3/4 1-19 3/4 1-25 3/4 1-25 3/4 1-26 3/4 1-26 3/4 1-27 3/4 1-27 3/4 1-28 3/4 1-28 3/4 1-29 3/4 1-29 3/4 1-30 3/4 1-30 3/4 1-33 3 /4 1 - 33 3/4 1-34 3/4 1-34 3/4 1-37 3/4 1-37 3/4 2-1 3/4 2-1 3/4 2-2 3/4 2-2 3/4 2-3 3/4 2-3 3/4 2-8 3/4 2-8 3/4 2-9 3/4 2-9 3/4 2-10 3/4 2-10 3/4 2-11 3/4 2-11 B 3/4 2-1 B 3/4 2-1 B 3/4 2-2 0 3/4 2 B 3/4 2-3 8 3/4 2-3 6-15 6-15 6-16 6-16

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DEFINITIONS SECTION gggg_

1.0 DEFINITIONS DEFINED TERMS 1-1 THERMAL POWER 1 - 1' RATED THERMAL POWER 1-1 OPERATIONAL MODE 1 ACTION 1-1 OPERABLE.- OPERABILITY 1-1 REPORTABLE EVENT 1-2 l.

CONTAINMENT INTEGRITY 1-2 CHANNEL CALIBRATION 1-2 CHANNEL CHECK 1-2 CHANNEL FUNCTIONAL TEST 1-3 CORE ALTERATION 1-3 SHUTDOWN MARGIN 1-3 IDENTFIED LEAKAGE 1-3 UNIDENTfFIED LEAKAGE 1-4 PRESSURE BOUNDARY LEAKAGE 1-4~

CONTROLLED LEAKAGE 1-4 QUADRANT POWER TILT 1-4 DOSE EQUIVALENT I-131 1-4 E-AVERAGE DISINTEGRATION ENERGY 1-4 STAGGERED TEST BASIS 1-5 FREQUENCY NOTATION 1-5 AXIAL POWER IMBALANCE 1-5 REACTOR PROTECTION SYSTEM RESPONSE TIME 1-5 ENGINEERED SAFETY FEATURE RESPONSE TIME 1-6 PHYSICS TESTS-1-6 SOURCE CHECK 1-6 l

l; PROCESS CONTROL PROGRAM (PCP) 1-6.

. SOLIDIFICATION 1-6 0FFSITE DOSE-CALCULATION MANUAL 1-6 CRYSTAL RIVER - UNIT 3 I

Amendment No. R$, %),90 1

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INDEX-DEFINITIONS SECTION PAGE 1.0 DEFINITIONS (Continued)

WASTE GAS SYSTEM...........................................

1-6 VENTILATION EXHAUST TREATMENT SYSTEM.......................

1-7 PURGE-PURGING..............................................

1-7 VENTING....................................................

1 -

INDEPENDENT VERIFICATION....................

'l - 7 LIQUID RADWASTE TREATMENT SYSTEM...........................

1-7 MEM'BER(S) 0F THEPUBLIC.....................................

1-8 SITE B0VNDARY..............................................

1-8 UNRESTRICTED AREA..........................................

1-8 CORE OPERATING LIMITS REP 0RT...............................

-l - 8 OPERATIONAL MODES (TABLE 1.1).............................

1-9 FREQUENCY NOTATION (TABLE 1.2).............................

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-CPVSTAl. iLVER - UNIT 3 la Amendment No. 69, 125

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IDEFINITIONS

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. -.,,.. - -. s 1.32 A VEtMILATIOM Y m OST T*.EATM"T SYSTEM is any systsm designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or EEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to release to the environment (such a system is not considered to have any i

i offact on noble gas offluents).

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXEADST TREATMENT SYSTEM components, i

1 PURGE - PURGING 1.33 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

VENTING 1.34 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidit concentration or other operating condition, in such a manner,y, L

that l

l replacement air or gas is not provided or required during

(

VENTING.

Vent, used in system names, does not imply a VENTING l

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process, l

INDEPENDENT VERIFICATION 1.35 INDEPENDENT VERIFICATICN is a separate act of confirming or substantiating that an activity or condition has been completed or implemented, in accordance with specified requirements, by an individual not associated with the original determination that the activity or condition was completed or implemented in accordance with specified requirements.

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LIQUID RADWASTE TREATMENT SYSTEM t

i 1.36 The LIQUID RADWASTE TREATMENT SYSTEM shall be any available j

equipment (e.g., filters, evaporators) capable of reducing the i

quantity of radioactive material, in liquid effluents, prior to discharge.

i CRYSTAL RIVER - UNIT 3 1-7 Amendment flo. 69 r

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..n DEFINITIONS MEMBER (S) 0F THE PUBLIC 1.37 MEMBER (S) 0F.THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant. =This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions.

This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their normal job function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.

SITE B0UNDARY 1.38 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.

UNRESTRICTED AREA 1.39 An UNRESTRICTED AREA shall be any area at or beyond the site boundary, access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the site boundary.used for residential quarters or industrial, commercial, institutional, and/or recreational purposes.

CORE OPERATING LIMITS REPORT

.1.40 The CORE OPERATING LIMITS REPORT is the unit specific document that provides core operating-limits for the current reload cycle.

These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.7.

Plant operation within these core operating limits is-addressed in individual specifications.

CRYSTAL RIVER - UNIT 3 1-8 Amendment No. 69, 125

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-REACTIVITY CONTROL-SYSTEMS ACTION: ~(Continued)

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A power distgibution map is obtained from the incore detectors and F and F H are verified to be within their limits within q

3 72 hourt,-and d)

The THERMAL F0WER level is reduced to < 60% of the THERMAL POWER allowable for the reactor coolant pump combination within; one hour and within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the Nuclear Overpower Trip Setpoint is reduced to 1 70% of the THERMAL POWER allowable for the reactor coolant pump combination, or e)

The remainder of the rods in the group with the inoperable rod are aligned to within + 6.5% of the inoperable rod within i

one hour while maintaining the position of the rods within the limits specified in the CORE OPERATING LIMITS REPORT.

The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6'during subsequent operation.

1 SURVEILLANCE REQUIREMENTS i

i 4.1.3.1.1 The position of each control rod shall be determined to be within the group average heightlimits by verifying the individual rod positions at least i

once per 12' hours except during time intervals when the Asymmetric Rod Monitor is 1

-inoperable, then verify. the individual rod positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each control rod not fully inserted shall be determined to be OPERABLE j

by movement of at least 3% in any one direction at least once every 31 days.

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i CRYSTAL RIVER - UNIT 3 3/4 1-19 Amendment No. 43, 77, 125

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REACTIVITY CONTROL SYSTEMS GROUP HEIGHT - AXTAL POWER SHAPING ROD GROUP s

LIMITING CONDITION FOR OPERATION 1

3.L.3.2 All axial power shaping rods (APSR) shall be OPERABLE. unless fully withdrawn, and shall be positioned within + 6.5% (indjcated position) of their group average height._

APPLICABILITY: MODES 1* and 2*,

ACTION:

With a maximum of one APSR inoperable or misaligned from its group i

average height by more than + 6.5% (indicated position), operation may continue ~ provided that withiii 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

The APSR group is positioned such that the misaligned rod is a.

restored to within limits for the group average height, or b.

It is determined that the imbalance limits of Specification 3.2.1 are satisfied and movement of the APSR group is pre-vented while the rod remains inoperable or misaligned.-

SURVEILLANCE REOUIREMENTS' 4.1.3.2.1 The position of each APSR red shall be determined to be within the group average height limit by verifying the individual rod positions at least-ence per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time' intervals when the Asyntetric Control Rod Monitor is inoperable, then verify the indi-vidual rod positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.2.2 Unless all APSR are fully withdrawn, each APSR shall be determined to be OPERABLE by moving the individual red at least 3%

at least once every 31 days.

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See Special Test Exceptions 3.10.1 and 3.10.2.

, CRYSTAL RIVER - UNIT 3 3/4 1-20 l

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REACTIVITY CONTROL SYSTEMS REGULATING R0D INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1. 3. 6 The regulating rod groups shall be positioned within the acceptable operating limits for regulating rod position specified in the CORE OPERATING LIMITS REPORT.

APPLICABILITY:

MODES 1* and 2*#,

ACTION:

With the regulating rod groups inserted in the unacceptable operation a.

region, immediately initiate and continue boration at greater than or equal to 10 GPM of 11,600 PPM boric acid solution or its equivalent, until out of the unacceptable operation region.

Additionally, either:

-1.

Restore the regulating groups to within the acceptable operating limits specified in the CORE OPERATING LIMITS REPORT within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of exceeding the acceptable operation region, or?

-2.

Reduce THERMAL POWER-to-less than or equal to that. fraction of RATED THERMAL POWER which is allowed by the-rod group position limits specified in the CORE OPERATING LIMITS REPORT within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of exceeding the acceptable operation region, or 3.

Be in at least H0T STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of exceeding the-acceptable operation region, b.

With the regulating rod groups inserted in the restricted operation

-region or-with any group sequence or overlap outside the acceptable operating limits specified in the CORE OPERATING LIMITS REPORT,-except for surveillance testing pursuant to Specification 4.1.2.1.2, either:

1.

Restore the regulating groups'to within the acceptable e

operating limits specified in the CORE OPERATING LIMITS REPORT l

within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s-of exceeding the acceptable operation region, or 2.

Reduce THERMAL POWER to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the rod group position limits specified in the CORE OPERATING LIMITS REPORT within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of exceeding the acceptable operation region, or 3.

Be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of exceeding the acceptable operation region.

See Special Test Exceptions 3.10.1 and 3.10.2.

With Keff greater than or equal to 1.0.

CRYSTAL RIVER - UNIT 3 3/4 1-25 Amendment No. 46,64,77,I03 125 l

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..i REACTIVITY ~ CONTROL SYSTEMS REGULATING ROD INSERTION LIMITS SURVEILLANCE REQUIREMENTS , 4.1.3.6 The position of each regulating group shall be determined to be 2

within the acceptable operating limits'specified in the CORE OPERATING LIMITS-REPORT at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except when:

a.

The regulating rod insertion limit alarm-is inoperable, then verify the groups to be within the insertion limits at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; b.

The control rod dri e sequence alarm is inoperable, then verify the groups to be within the sequence and overlap limits at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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REACTIVITY CONTROL SYSTEMS

.R0D PROGRAM LIMITING CONDITION FOR OPERATION 3.1.3.7 -Each control rod assembly (safety, regulating and APSR) shall be pro-s grammed to operate in the core location and rod group specified in the CORE OPERATING LIMITS REPORT.

APPLICABILITY:

MODES 1* and 2*.

ACTION:

With any control rod not programmed to operate as specified above, be in HOT STAND 8Y within I hour.

SURVEILLANCE REQUIREMENTS 4.1.3.7-Each control rod assembly shall be demonstrated to be programmed to l

a.

operate in the specified core location and rod group by:

1 1.

Selection and actuation from the control room and verifi-

-cation of movement'of the proper rod as indicated by both the g

absolute and relative location indicators:

I a)

For all control rod assemblies, after the control rod drive l

patchs are locked subsequent to test, reprogramming or maintenance within the panels.

b)

For specifically affected individual rod assemblies l

following maintenance, test, reconnection or modification of power or instrumentation cables from the control rod drive control system to the control rod drive.

2.

Verifying that each cable that has been disconnected has been properly matched and reconrected to the specified control rod drive, b.

At least once each 7 days, verify that the control rod drive patch panels are locked.

See Special Test Exceptions 3.10.1 and 3.10.2.

CRYSTAL RIVER - UNIT 3 3/4 1-33 Amendment No. Ig, 125

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REACTIVITY CONTROL SYSTEMS AXIAL POWER SHAPING ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1. 3. 9 Except as required for surveillance testing per Technical Specification 3.1.3.3, the axial power shaping rod (APSR) insertion limits shall be within the acceptable operating limits specified in the CORE OPERATING LIMITS REPORT.

APPLICABILITY:

MODES 1 and 2*.

ACTION:

With the axial power shaping rod group outside the acceptable operating insertion limits specified in the CORE OPERATING LIMITS REPORT, either:

Restore the axial power shaping rod group to within the acceptable a.

operating limits specified in the CORE OPERATING t.IMITS REPORT within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or b.

Reduce THERMAL POWER to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the rod group position limits l

specified in the CORE OPERATING LIMITS REPORT within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or c.

Be in at least H0T STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE0VIREMENTS 4.1.3.9 The position of the axial power shaping rod group shall be. determined to be within the acceptable operating limits specified in the CORE OPERATING LIMITS REPORT at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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LIMITING CONDITION FOR OPERATION A-Q:W'

~3.2.1 AXIAL POWER IMBALANCE'shall be maintained within the acceptable AXIAL POWER' IMBALANCE operating limits specified in the CORE OPERATING LIMITS.

REPORT.

APPLICABILITY:

MODE 1 above 40% of RATED THERMAL POWER.*

ACTION:

'With AXIAL POWER IMBALANCE exceeding the limits specified above, either:

a.

-Restore the AXIAL POWER IMBALANCE to within acceptable operating limits specified in the CORE OPERATING LIMITS REPORT within 15 minutes, or-b.

Be'in at least HOT STANDBY within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

r SURVEILLANCE REQUIREMENTS 4.2.1 The AXIAL POWER IMBALANCE shall_ be determined to be within acceptable operating limits specified in the CORE OPERATING LIMITS REPORT in each core quadrant at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when above 40% of RATED THERMAL POWER except when an AXIAL POWER IMBALANCE monitor is inoperable, then calculate the AXIAL POWER IMBALANCE in each core quadrant with an inoperable monitor at 11 east once per hour.

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See Special Test Exception 3.10.1.

CRYSTAL RIVER - UNIT 3 3/4 2-1 Amendment No. 46,77,103, 125 a

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,0 POWER DISTRIBUTION LIMITS

-SURVEILLANCE REQUIREMENTS.

U 4.2.3.1 F shall be determined to be within its limit by using the incore detectors to obtain a power distribution map:

-c a._

Prior to operation above 75 percent of RATED THERMAL POWER

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'af ter each fueliloading, and-b.'

At least once per 31 Effective Full Power Days.

The provisions of Specification 4.0.4 are not applicable.

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4.2.3.2 The measured FN formeasurementuncertaNty.of 4.2.3.1 above, shall be increased by 5%

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L POWER DISTRIBUTION LIMITS QUADRANT POWER TILT LIMITING CONDITION FOR OPERATION 3.2.4 THE QUADRANT POWER TILT shall be maintaineu < the steady state limits for QUADRANT POWER TILT specified in the CORE OPERATING LIMITS REPORT.

APPLICABILITY:

MODE 1 above 15% of RATED THERMAL POWER.*

ACTION:

With the QUADRANT POWER TILT determined to exceed the Steady State a.

Limit but less than or equal to the Transient Limit specified in the CORE OPERATING LIMITS REPORT.

l 1.

Within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

a)

Either reduce the QUADRANT POWER TILT to within its Steady State Limit, or b)

Reduce THERMAL POWER so as not to exceed THERMAL POWER, including power level cutoff, allowable for the reactor coolant pump combination less at least 2% for each 1% of QUADRANT POWER TILT in excess of the Steady State Limit and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , reduce the Nuclear Overpower Trip Setpoint and the Nuclear Overpower Based on RCS Flow and AXIAL POWER IMBALANCE Trip Setpoint at least 2% for each 1% of QUADRANT POWER TILT in excess of the Steady State Limit.

2.

Verify that the QUADRANT POWER TILT is within its Steady State Limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding the Steady State Limit or reduce THERMAL POWER to less than 60% of THERMAL POWER allowable for the reactor coolant pump combination within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Nuclear Overpower Trip Setpoint to < 65.5% of THERMAL POWER allowable for the reactor coolant puiiip combination within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 60% of THERMAL POWER allowable for the reactor coolant pump combination may proceed provided that the QUADRANT POWER TILT is verified within its Steady State Limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified acceptable at 95% or greater RATED THERMAL POWER.

See Special Test Exception 3.10.1.

CRYSTAL RIVER - UNIT 3 3/4 2-8 Amendment No. 125 1

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'o, POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued) b.

With the QUADRANT POWER TILT determined to exceed the Transient Limit but less than the Maximum Limit specified in the CORE l

OPERAllNG LIMITS REPORT, due to misalignment of either a safety, regulating or axial power shaping rod:

1.

Reduce THERMAL POWER at least 2% for each 1% of indicated QUADRANT POWER TILT in excess of the Steady State Limit within 30 minutes.

2.

Verify that the QUADRANT POWER TILT is within its Transient Limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after exceeding the Transient Limit or reduce THERMAL POWER to less than 60% of THERMAL POWER allowable for the reactor coolant pump combination within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Nuclear Overpower Trip Setpoint to < 65.5% of THERMAL POWER allowable for the reactor coolant pump combination within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3.

Identify and correct the cause of the out of limit con-dition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 60% of THERMAL POWER allowable for the reactor coolant pump combination may proceed provided that the QUADRANT POWER TILT is verified within its Steady State Limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified acceptable at 95% or greater RATED THERMAL POWER.

c.

With the QUADRANT POWER TILT determined to exceed the Transient Limit but less than the Maximum Limit specified in the CORE OPERATING LIMITS REPORT, due to causes other than the misalignment of either a safety, regulating or axial power shaping rod:

1.

Reduce THERMAL POWER to less than 60% of THERMAL POWER allowable for the reactor coolant pump combination within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Nuclear Overpower Trip Setpoint to < 65.5% of THERMAL POWER allowable for the reactor cooTant pump combination within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

2.

Identify and correct the cause of the out of limit con-dition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 60% of THERMAL POWER allowable for the reactor coolant pump combination may proceed provided that the QUADRANT POWER TILT is verified within its Steady State Limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified at 95% or greater RATED THERMAL POWER.

CRYSTAL. RIVER - UNIT 3 3/4 2-9 Amendment No. 125

.o s

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continued) d.

With the QUADRANT POWER TILT determined to exceed the Maximum Limit specified in the CORE OPERATING LIMITS REPORT, reduce THERMAL POWER to < 15% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SURVEILLANCE REQUIREMENTS 4.2.4 The QUADRANT POWER TILT shall be determined to be < the steady state limits specified in the CORE OPERATING LIMITS REPORT at least once every 7 days during operation above 15% of RATED THERMAL POWER except when the QUADRANT POWER TILT monitor is inoperable, then the QUADRANT POWER TILT shall be calculated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

CRYSTAL RIVER - UNIT 3 3/4 2-10 Amendment No. 125

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I' i

CRYSTAL RIVER - UNIT 3 3/4 2-11 Amendment No. JE,1),72,77,Jp3,125 i

i l

f Pewta etstatstttow t!wtis DNB DatAut"Its LIMITIN3 CDN0! TION FCR OP[t,ATION e

i 3.2.5 The following DNS related parameters shall be Atintainec within the limits shown on Table 3.2 1:

a.

Reactor Coolant Het Leg Temperature

~

b.

Reactor Coolant Pressure c.

Reactor Coolant Flow Rate l

APPLICA8!LITY: M00[ 1.

ACTION:

With any of the above parasuters exceeding its limit. restore the param-eter to within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce TkERMal POWEA to less than it of RATED THERMAL POWER within the next a hours.

I

$URV!!!,1,ANCE R[30!REMENTI 4.2.5.1 tach of the parameters of Table 3.21 shall be verified to be within their limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.2.5.2 The Reactor Coolant System total flow rate shall be detemined-l-

to be within its limit by measurement at least once per 18 months.

I 9

CRT57AL RIVER. UNIT 3 3/4 2 12

3/4.2 POWER DISTRIBUTION LIMITS BASES r

The specifications of this section provide assurance of fuel integrity during Condition I (Normal Operation) and II (Incidents of Moderate Frequency) events by:

(a) maintaining the minimum DNBR in the core within the limit during normal operation and during short term transients, (b) maintaining the peak linear power density s 18.0 kw/ft during normal operation, and (c) maintaining the peak power density s 20.5 kw/ft during short term transients.

In addition, the above criteria must be met in order to meet the assumptions used for the loss-of-coolant accidents.

The power imbalance envelope and the insertion limit curves, defined in the CORE OPERATING LIMITS REPORT (COLR), are based on LOCA analyses which have defined the maximum linear heat rate such that the maximum clad temperature will not exceed the Final Acceptance Criteria of 2200*F following a LOCA.

Operation outside of the power-imbalance envelope alone does not constitute a situation that would cause the Final Acceptance Criteria to be exceeded should a LOCA occur. The power-imbalance envelope represents the boundary of operation limited by the Final Acceptance Criteria only if the control rods are at the insertion limits, as defined in the COLR, and if the steady state l

limit QUADRANT POWER TILT exists. Additional conservatism is introduced by application of:

a.

Nuclear uncertainty factors.

b.

Thermal calibration uncertainty.

c.

Fuel densification effects, d.

Hot rod manufacturing tolerance factors.

The conservative application of the above peaking augmentation factors considers the potential peaking penalty due to fuel rod blow.

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original criteria are met.

The definitions of the design limit nuclear power peaking factors as used in these specifications are as follows:

Fg Nuclear Heat Flux Hot Channel Factor, is defined as the maximum i

local fuel rod linear power density divided by the average fuel rod i

linear power density, assuming nominal fuel pellet and rod l

dimensions.

l l

CRYSTAL RIVER - UNIT 3 8 3/4 2-1 Amendment No. 16,77,703, 125

f E0WER DISTRIBUTION LIMITS BASES FN Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of AH the integral of linear power along the rod on which minimum DNBR occurs to the average rod power.

It has been determined by extensive analysis of possible operating power shapes that the design limits on nuclear power peaking and on minimum DNBR at full power are met, provided:

Fg 5 3.13; FN s 1,71 LH Power Peaking is not a directly observable quantity and therefore limits have been established on the bases of the AXIAL POWER IMBALANCE produced by the power peaking, it has been determined that the above hot channel factor limits will be met provided the following conditions are maintained.

1.

Control rods in a single group move together with no individual rod insertion differing by more than 6.5% (indicated position) from the group average height.

2.

Regulating rod groups are sequenced with overlapping groups as required in Specification 3.1.3.6.

3.

The regulating rod insertion limits of Specification 3.1.3.6 and the axial power shaping rod insertion limits of Specification 3.1.3.9 are maintained.

4.

AXIAL POWER IMBALANCE limits are maintained.

THE AXIAL POWER IMBALANCE is a measure of the difference in power between the top and bottom halves of the core.

Calculations of core average axial peaking factors for many plants and measurements from operating plants under a variety of operating conditions have been correlated with AXIAL POWER IMBALANCE.

The correlation shows that the design power shape is not exceeded if the AXIAL POWER IMBALANCE is maintained within the limits defined in the n

l COLR.

l The design limit power peaking factors are the most restrictive calculated at full power for the range from all control rods fully withdrawn to minimum allowable control rod insertion and are the core DNBR design basis.

Therefore, for operation at a fraction of RATED THERMAL POWER, the design limits are met. When using incore detectors to make power distribution maps to determine FQ and FN:

The measurement of total peaking factor, FgMeas, shall be increased a.

by 1.4 percent to account for manufacturing tolerances and further increased by 7.5 percent to account for measurement error.

CRYSTAL RIVER - UNIT 3 8 3/4 2-2 Amendment No. 76,79,77,7N, 125

L POWER DISTRIBUTION LIMITS BASES I

b.

The measurement of enthalpy rise hot channel factor F

, shall be increased by 5 percent to account for measurement error.

For Condition 11 events, the core is protected from exceeding allowable fuel melt limit locally, and from going below minimum allowable DNBR by automatic protection on power, AXIAL POWER IMBALANCE, pressure and temperature.

Only conditions 1 through 3, above, are mandatory since the AXIAL POWER IMBALANCE is an explicit input to the Reactor Protection System.

The QUADRANT POWER TILT limit assures that the radial power distribution satisfies the design values used in the power capability analysis.

Radial power distribution measurements are made during startup testing and periodically during power operation.

For QUADRANT POWER TILT, the safety (measurement independent) limits for Steady State, Transient State, and the Maximum Limit are defined in the COLR.

The QUADRANT POWER TILT limit at which corrective action is required provides DNB and linear heat generation rate protection with x-y plane power tilts.

The limit was selected to provide an allowance for the uncertainty associated with the power tilt.

In the event the tilt is not corrected, the margin for uncertainty on Fg is reinstated by reducing the power by 2 percent for each percent of tilt in excess of the limit.

3/4 2.5 DNB PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the normai steady state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the FSAR initial assumptions and have been analytically demonstrated adequate to maintain.a DNBR within the limit throughout each analyzed transient.

The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation.

The 18 month periodic measurement of the RCS total flow rate is adequate to detect flow degradation and ensure correlation of the flow indication channels with measured flow such that the indicated percent flow will provide sufficient verification of flow rate on a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months basis.

l CRYSTAL RIVER - UNIT 3 B 3/4 2-3 Amendment No. 77,77,70, 125 L

I ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT

6. 9.1. 6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Document Control Desk, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, with a copy to the Regional Office, submitted no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT

6. 9.1. 7 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle and any remaining part of a reload cycle for the following:

3.1.3.6 Regulating Rod Insertion Limits 3.1.3.7 Rod Program 3.1.3.9 Axial Power Shaping Rod Insertion Limits 3.2.1 AXIAL POWER IMBALANCE 3,2,4 QUADRANT POWER TILT The analytical methods used to determine the core operating limits addressed by the individual Technical Specifications shall be those previously reviewed and approved by the NRC, specifically:

1)

BAW-10122A Rev. 1, " Normal Operating Controls", May 1984 2)

BAW-10116A, " Assembly Calculations and fitted Nuclear Data", May 1977 3)

BAW-10117P-A, " Babcock & Wilcox Version of PDQ User's Manual",

January 1977 4)

BAW-10118A, " Core Calculational Techniques and Procedures",

December 1979.

5)

BAW-10124A, " FLAME 3 - A Three-Dimensional Nodal Code for Calculating Core Reactivity and Power Distributions", August 1976 6)

BAW-10125A, " Verification of Three-Dimensional FLAME Code".

August 1976 l

7)

BAW-10152A, "N0ODLE - A Multi-Dimensional Two-Group Reactor Simulator", June 1985 8)

BAW-10119, " Power Peaking Nuclear Reliability Factors", June 1977 9)

The methodology for Rod Program received NRC approval in the Safety Evaluation Report dated (

).

The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal mechanical limits, core thermal-hydraulic limits, ECCS l

CRYSTAL RIVER - UNIT 3 6-15 Amendment No. 9.49,90, Ill, 125

r ADMINISTRATIVE CONTROLS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

The CORE OPERATING LIMITS REPORT, including any mid-cycle revision or supple-ments thereto. shall be provided upon issuance for each reload cycle to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

s i

I CRYSTAL RIVER - UNIT 3 6-16 Amendment No. 9,25,69,90, 125

ML20011E465

Text

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